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华龙一号国际审查认证中结构完整性领域的实践和思考

毛庆 张涛 徐晓 岑鹏 王国锋

毛庆, 张涛, 徐晓, 岑鹏, 王国锋. 华龙一号国际审查认证中结构完整性领域的实践和思考[J]. 核动力工程, 2024, 45(2): 1-9. doi: 10.13832/j.jnpe.2024.02.0001
引用本文: 毛庆, 张涛, 徐晓, 岑鹏, 王国锋. 华龙一号国际审查认证中结构完整性领域的实践和思考[J]. 核动力工程, 2024, 45(2): 1-9. doi: 10.13832/j.jnpe.2024.02.0001
Mao Qing, Zhang Tao, Xu Xiao, Cen Peng, Wang Guofeng. Practice and Learning in the Field of Structural Integrity during the HPR1000 International Regulatory and Certified Review[J]. Nuclear Power Engineering, 2024, 45(2): 1-9. doi: 10.13832/j.jnpe.2024.02.0001
Citation: Mao Qing, Zhang Tao, Xu Xiao, Cen Peng, Wang Guofeng. Practice and Learning in the Field of Structural Integrity during the HPR1000 International Regulatory and Certified Review[J]. Nuclear Power Engineering, 2024, 45(2): 1-9. doi: 10.13832/j.jnpe.2024.02.0001

华龙一号国际审查认证中结构完整性领域的实践和思考

doi: 10.13832/j.jnpe.2024.02.0001
详细信息
    作者简介:

    毛 庆(1969—),男,正研级高级工程师,现主要从事工程力学方面的研究,E-mail: maoqing2009@cgnpc.com.cn

  • 中图分类号: TL48

Practice and Learning in the Field of Structural Integrity during the HPR1000 International Regulatory and Certified Review

  • 摘要: 为促进国际市场开发,中国广核集团有限公司开展了华龙一号核电技术方案英国通用设计审查(GDA)和欧洲用户要求认证(EUR)。核电厂构筑物、系统和设备的结构完整性是国际审查和认证的重点,为适应英国核安全监管和欧洲用户要求,项目团队采用分析法设计理念,以力学分析、试验和论证为关键手段,完成了英国版和欧洲版华龙一号的结构完整性分析评估和设计改进,全面满足了英国核安全监管和欧洲用户要求。通过华龙一号国际审查和认证,研究了结构完整性领域的相关技术要求,总结了审查过程中的实践和思考,可为华龙一号核电技术方案的持续改进和创新提供借鉴。

     

  • 图  1  Safety Case的CAE结构

    Figure  1.  CAE Structure in Safety Case

    图  2  考虑埋置效应计算模型

    Figure  2.  Calculation Model Considering the Embedded Effect  

    图  3  埋置效应对楼层反应谱的影响对比

    g—重力加速度

    Figure  3.  Comparison of Floor Response Spectra with or without Considering Embedded Effect  

    图  4  结构-土-结构相互作用敏感性分析模型

    Figure  4.  Sensitivity Study of SSSI Effect

    图  5  不同地基土条件下结构-土-结构相互作用影响分析结果对比

    Figure  5.  Comparison of SSSI Effect Analysis Results for Different Soil Stiffness

    图  6  飞机撞击数值模拟分析

    Figure  6.  Numerical Simulation Analysis for Aircraft Impact

    图  7  安全壳建模分解图

    Figure  7.  Containment Modeling Breakdown Diagram

    图  8  截锥体区域设计简化图

    Figure  8.  Simplified Diagram of Truncated Cone Area Design

    图  9  安全壳应力云图

    Figure  9.  Containment Stress Distribution

    图  10  反应堆压力容器顶盖跌落和乏燃料罐跌落对结构影响评价

    Figure  10.  Structural Assessment of Dropped Load by Reactor Pressure Vessel Head Assembly and Spent Fuel Cask

    图  11  高能管道失效甩击设备分析(蒸汽发生器下封头)

    Figure  11.  Analysis of High Energy Pipe Failure Whip Impacting on Equipment (SG Lower Head)

    图  12  重物跌落冲击设备分析(反应堆压力容器)

    Figure  12.  Analysis of Heavy Load Dropped Impacting on Equipment (RPV)  

    图  13  失效评定图和极限裂纹尺寸示意图

    Lr—载荷比;Kr—断裂比;Lr-Max—Lr的容许极限;FAC—失效评定曲线;f(Lr)—关于Lr的函数     

    Figure  13.  FAD and Limiting Defect Size

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出版历程
  • 收稿日期:  2023-12-05
  • 修回日期:  2023-12-25
  • 刊出日期:  2024-04-12

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